Published 1984
| Version v1
Report
Restricted
Analysis of H.B. Robinson Unit-2 pressurized thermal shock transients
Description
In support of the USNRC PTS Integration Study for the resolution of USI A-49, analyses were performed of 180 overcooling sequences that were defined by ORNL for the H.B. Robinson Unit-2 (HBR-2) plant. The analyses produced vessel downcomer temperature, pressure and heat transfer coefficient histories (the primary parameters of interest for PTS) for the 180 overcooling sequences. The information was used to perform fracture mechanics and multidimensional effects analyses to determine for each sequence the probability of vessel failure
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE85003409.
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- EGG-M--18284
Conference
- Title
- 12. water reactor safety research information meeting.
- Dates
- 23-26 Oct 1984.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16054714
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOSS OF COOLANT; ROBINSON-2 REACTOR; RUPTURES; STEAM GENERATORS; STEAM LINES; THERMAL SHOCK; TRANSIENTS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; ENRICHED URANIUM REACTORS; FAILURES; PIPELINES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8410142--56.